US4735768A - Fuel rod for a nuclear reactor fuel assembly - Google Patents
Fuel rod for a nuclear reactor fuel assembly Download PDFInfo
- Publication number
- US4735768A US4735768A US06/894,922 US89492286A US4735768A US 4735768 A US4735768 A US 4735768A US 89492286 A US89492286 A US 89492286A US 4735768 A US4735768 A US 4735768A
- Authority
- US
- United States
- Prior art keywords
- zirconium alloy
- iron
- weight
- fuel rod
- fuel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- Such fuel rods are in common use. They are built into the frame of the nuclear reactor fuel assembly. This nuclear reactor fuel assembly is finally inserted into a nuclear reactor, in which it is cooled, for instance, with light water. In this nuclear reactor, the zirconium alloys of the cladding tubes have a relatively small capture cross section for thermal neutrons.
- a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube comprising an inner tubular layer formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.07 to 0.2% iron, 0.05 to 0.15% chromium, 0.03 to 0.08% nickel, 0.07 to 0.15% oxygen, with the sum of percentages for the alloying components iron, chromium and nickel in the range of 0.18 to 0.38%; the combination therewith of a surface layer on the outside of the inner tubular layer of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight
- a fuel rod for a nuclear reactor fuel assembly with nuclear fuel which is contained in a cladding tube comprising an inner tubular layer formed of a zirconium alloy with alloying components based on the weight of the zirconium alloy of 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium, 0.10 to 0.16% oxygen, with the sum of percentages for the alloying components iron, and chromium in the range of 0.28 to 0.37%; the combination therewith of a surface layer on the outside of the inner tubular layer of a second zirconium alloy with a layer thickness in the range of 5 to 20% of the total wall thickness of the cladding tube as well as with 0 to 1% by weight iron based on the second zirconium alloy as an alloying component and with at least one alloying component selected from the group consisting of vanadium, platinum and copper wherein the amounts by weight based on the second zirconium alloy are: vanadium--0.1
- the invention is based on the insight that the zirconium alloy of which the surface layer on the outside of the cladding tube of this fuel rod consists, is more corrosion-resistant than the zirconium alloy of which the rest of the cladding tube consists. While furthermore, the capture cross section of vanadium, platinum and copper for thermal neutrons is relatively large and the three mentioned alloying components are present only in the relatively thin surface layer of the cladding tube, the absorption losses of thermal neutrons in the nuclear reactor due to the cladding tubes are nevertheless relatively small.
- Tests in an autoclave showed that the rate of corrosion of a test specimen of a zirconium alloy with 0.5% by weight iron and 0.25% by weight vanadium as the alloying components in steam is only one-tenth of the corrosion rate of a test specimen of a zirconium alloy with the trade name Zircaloy 4 under the same conditions, which contains, besides the zirconium, 1.2 to 1.7% tin, 0.18 to 0.24% iron, 0.07 to 0.13% chromium and 0.1 to 0.16% oxygen as further alloying components and in which the sum of the percentages by weight of the alloying components iron and chromium is in the range from 0.28 to 0.37% by weight.
- the dwelling time of a nuclear reactor fuel assembly with fuel rods according to the invention in a nuclear reactor can therefore be at least one year longer than that of a nuclear reactor fuel assembly with fuel rods, the cladding tubes of which consist of Zircaloy 4.
- a tube blank which comprises an inner tube, for instance, of Zircaloy 4 and an outer tube placed on this inner tube, of the zirconium-vanadium-iron alloy with 0.5% by weight iron and 0.25% by weight vanadium.
- This tube blank is heated to a temperature in the range of 500° to 700° C. and is then extruded. In the process, a metallurgical compound between the two zirconium alloys results.
- the final cladding tube for the fuel rod is ultimately obtained, which can, for instance, have a diameter of 10.7 mm and a wall thickness of 0.72 mm.
- the surface layer of the vanadium-containing zirconium alloy cover the entire outside of this cladding tube and may be, for instance, 0.1 mm thick.
- a pilger-rolling mill is described, for instance, in U.S. Pat. No. 42 33 834.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Metallurgy (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Catalysts (AREA)
Abstract
Description
Claims (8)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE3528545 | 1985-08-08 | ||
DE19853528545 DE3528545A1 (en) | 1985-08-08 | 1985-08-08 | FUEL ROD FOR A CORE REACTOR FUEL |
Publications (1)
Publication Number | Publication Date |
---|---|
US4735768A true US4735768A (en) | 1988-04-05 |
Family
ID=6278075
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US06/894,922 Expired - Lifetime US4735768A (en) | 1985-08-08 | 1986-08-08 | Fuel rod for a nuclear reactor fuel assembly |
Country Status (4)
Country | Link |
---|---|
US (1) | US4735768A (en) |
EP (1) | EP0212351B1 (en) |
JP (1) | JPH065311B2 (en) |
DE (2) | DE3528545A1 (en) |
Cited By (25)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4775508A (en) * | 1985-03-08 | 1988-10-04 | Westinghouse Electric Corp. | Zirconium alloy fuel cladding resistant to PCI crack propagation |
US4816214A (en) * | 1987-10-22 | 1989-03-28 | Westinghouse Electric Corp. | Ultra slow EB melting to reduce reactor cladding |
US4933136A (en) * | 1985-03-08 | 1990-06-12 | Westinghouse Electric Corp. | Water reactor fuel cladding |
US4938921A (en) * | 1987-06-23 | 1990-07-03 | Framatome | Method of manufacturing a zirconium-based alloy tube for a nuclear fuel element sheath and tube thereof |
US4938920A (en) * | 1988-02-18 | 1990-07-03 | Siemens Aktiengesellschaft | Nuclear reactor fuel assembly |
US4963316A (en) * | 1987-07-21 | 1990-10-16 | Siemens Aktiengesellschaft | Fuel rod for a nuclear reactor fuel assembly |
US4986957A (en) * | 1989-05-25 | 1991-01-22 | General Electric Company | Corrosion resistant zirconium alloys containing copper, nickel and iron |
US5024809A (en) * | 1989-05-25 | 1991-06-18 | General Electric Company | Corrosion resistant composite claddings for nuclear fuel rods |
US5026516A (en) * | 1989-05-25 | 1991-06-25 | General Electric Company | Corrosion resistant cladding for nuclear fuel rods |
US5073336A (en) * | 1989-05-25 | 1991-12-17 | General Electric Company | Corrosion resistant zirconium alloys containing copper, nickel and iron |
US5084234A (en) * | 1988-12-31 | 1992-01-28 | Hoesgen Karlheinz | Absorption casing for a source of radioactive radiation, particularly for a nuclear reactor |
WO1993018520A1 (en) * | 1992-03-13 | 1993-09-16 | Siemens Aktiengesellschaft | Nuclear reactor fuel rod with double layer cladding tube |
US5247550A (en) * | 1992-03-27 | 1993-09-21 | Siemens Power Corporation | Corrosion resistant zirconium liner for nuclear fuel rod cladding |
US5373541A (en) * | 1992-01-17 | 1994-12-13 | Framatome | Nuclear fuel rod and method of manufacturing the cladding of such a rod |
US5711826A (en) * | 1996-04-12 | 1998-01-27 | Crs Holdings, Inc. | Functionally gradient cladding for nuclear fuel rods |
US5768332A (en) * | 1997-03-27 | 1998-06-16 | Siemens Power Corporation | Nuclear fuel rod for pressurized water reactor |
US5772798A (en) * | 1997-03-25 | 1998-06-30 | Siemens Power Corporation | High strength zirconium alloys containing bismuth |
US5787142A (en) * | 1997-04-29 | 1998-07-28 | Siemens Power Corporation | Pressurized water reactor nuclear fuel assembly |
US5790623A (en) * | 1997-03-25 | 1998-08-04 | Siemens Power Corporation | Composite cladding for nuclear fuel rods |
US5887045A (en) * | 1995-01-30 | 1999-03-23 | Framatome | Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same |
US6511556B1 (en) | 1998-06-12 | 2003-01-28 | Siemens Power Corporation | High strength zirconium alloys containing bismuth and niobium |
US20050005872A1 (en) * | 2003-07-09 | 2005-01-13 | Greeson John Stuart | Automated carrier-based pest control system |
US20060048869A1 (en) * | 2004-09-08 | 2006-03-09 | David White | Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same |
US20060048870A1 (en) * | 2004-09-08 | 2006-03-09 | David White | Zirconium alloy fuel cladding for operation in aggressive water chemistry |
US20110002433A1 (en) * | 2006-08-24 | 2011-01-06 | Lars Hallstadius | Water Reactor Fuel Cladding Tube |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2642215B1 (en) * | 1989-01-23 | 1992-10-02 | Framatome Sa | PENCIL FOR FUEL ASSEMBLY OF A CORROSION AND WEAR RESISTANT NUCLEAR REACTOR |
FR2663115B1 (en) * | 1990-06-08 | 1994-04-15 | Framatome | METHOD AND DEVICE FOR CONTROLLING THE THICKNESS AND THE COHESION OF THE INTERFACE OF A DUPLEX TUBE. |
EP1760724A3 (en) | 1999-03-29 | 2009-03-18 | AREVA NP GmbH | Fuel element for a pressurised water reactor and method for producing the cladding tubes thereof |
Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH387180A (en) * | 1958-02-27 | 1965-01-31 | Atomic Energy Commission | Nuclear reactor fuel element and method of manufacturing the fuel element |
FR1537960A (en) * | 1967-07-20 | 1968-08-30 | Siemens Ag | Process for obtaining high corrosion resistance |
LU53851A1 (en) * | 1967-06-09 | 1969-04-22 | ||
US3620691A (en) * | 1964-04-11 | 1971-11-16 | Siemens Ag | Zirconium structure |
FR2317372A1 (en) * | 1975-06-26 | 1977-02-04 | Gen Electric | PROCESS FOR IMPROVING THE CORROSION RESISTANCE OF ZIRCONIUM ALLOY PARTS AND PARTS THUS OBTAINED. |
US4045288A (en) * | 1974-11-11 | 1977-08-30 | General Electric Company | Nuclear fuel element |
US4233834A (en) * | 1979-01-26 | 1980-11-18 | Sandvik Special Metal Corporation | Method and apparatus for producing zircaloy tubes and zircaloy tubes thus produced |
FR2509510A1 (en) * | 1981-07-07 | 1983-01-14 | Asea Atom Ab | METHOD FOR MANUFACTURING COATING TUBES IN A ZIRCONIUM-BASED ALLOY FOR FUEL BARS FOR NUCLEAR REACTORS |
US4406012A (en) * | 1974-11-11 | 1983-09-20 | General Electric Company | Nuclear fuel elements having a composite cladding |
US4411861A (en) * | 1977-08-19 | 1983-10-25 | Kraftwerk Union Aktiengesellschaft | Method for protecting the casing tubes of nuclear reactor fuel rods |
FR2538940A1 (en) * | 1982-12-30 | 1984-07-06 | Kraftwerk Union Ag | METHOD FOR MAKING A ZIRCONIUM ALLOY SHEATH FOR THE FUEL OF A NUCLEAR REACTOR COMBUSTIBLE ELEMENT |
US4473410A (en) * | 1977-08-01 | 1984-09-25 | General Electric Company | Nuclear fuel element having a composite coating |
-
1985
- 1985-08-08 DE DE19853528545 patent/DE3528545A1/en not_active Withdrawn
-
1986
- 1986-07-28 EP EP86110396A patent/EP0212351B1/en not_active Expired - Lifetime
- 1986-07-28 DE DE8686110396T patent/DE3668251D1/en not_active Revoked
- 1986-08-01 JP JP61181811A patent/JPH065311B2/en not_active Expired - Lifetime
- 1986-08-08 US US06/894,922 patent/US4735768A/en not_active Expired - Lifetime
Patent Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH387180A (en) * | 1958-02-27 | 1965-01-31 | Atomic Energy Commission | Nuclear reactor fuel element and method of manufacturing the fuel element |
US3620691A (en) * | 1964-04-11 | 1971-11-16 | Siemens Ag | Zirconium structure |
LU53851A1 (en) * | 1967-06-09 | 1969-04-22 | ||
FR1537960A (en) * | 1967-07-20 | 1968-08-30 | Siemens Ag | Process for obtaining high corrosion resistance |
US4045288A (en) * | 1974-11-11 | 1977-08-30 | General Electric Company | Nuclear fuel element |
US4406012A (en) * | 1974-11-11 | 1983-09-20 | General Electric Company | Nuclear fuel elements having a composite cladding |
FR2317372A1 (en) * | 1975-06-26 | 1977-02-04 | Gen Electric | PROCESS FOR IMPROVING THE CORROSION RESISTANCE OF ZIRCONIUM ALLOY PARTS AND PARTS THUS OBTAINED. |
US4473410A (en) * | 1977-08-01 | 1984-09-25 | General Electric Company | Nuclear fuel element having a composite coating |
US4411861A (en) * | 1977-08-19 | 1983-10-25 | Kraftwerk Union Aktiengesellschaft | Method for protecting the casing tubes of nuclear reactor fuel rods |
US4233834A (en) * | 1979-01-26 | 1980-11-18 | Sandvik Special Metal Corporation | Method and apparatus for producing zircaloy tubes and zircaloy tubes thus produced |
FR2509510A1 (en) * | 1981-07-07 | 1983-01-14 | Asea Atom Ab | METHOD FOR MANUFACTURING COATING TUBES IN A ZIRCONIUM-BASED ALLOY FOR FUEL BARS FOR NUCLEAR REACTORS |
FR2538940A1 (en) * | 1982-12-30 | 1984-07-06 | Kraftwerk Union Ag | METHOD FOR MAKING A ZIRCONIUM ALLOY SHEATH FOR THE FUEL OF A NUCLEAR REACTOR COMBUSTIBLE ELEMENT |
Cited By (30)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4933136A (en) * | 1985-03-08 | 1990-06-12 | Westinghouse Electric Corp. | Water reactor fuel cladding |
US4775508A (en) * | 1985-03-08 | 1988-10-04 | Westinghouse Electric Corp. | Zirconium alloy fuel cladding resistant to PCI crack propagation |
US4938921A (en) * | 1987-06-23 | 1990-07-03 | Framatome | Method of manufacturing a zirconium-based alloy tube for a nuclear fuel element sheath and tube thereof |
US4963316A (en) * | 1987-07-21 | 1990-10-16 | Siemens Aktiengesellschaft | Fuel rod for a nuclear reactor fuel assembly |
US4816214A (en) * | 1987-10-22 | 1989-03-28 | Westinghouse Electric Corp. | Ultra slow EB melting to reduce reactor cladding |
US4938920A (en) * | 1988-02-18 | 1990-07-03 | Siemens Aktiengesellschaft | Nuclear reactor fuel assembly |
US5084234A (en) * | 1988-12-31 | 1992-01-28 | Hoesgen Karlheinz | Absorption casing for a source of radioactive radiation, particularly for a nuclear reactor |
US4986957A (en) * | 1989-05-25 | 1991-01-22 | General Electric Company | Corrosion resistant zirconium alloys containing copper, nickel and iron |
US5024809A (en) * | 1989-05-25 | 1991-06-18 | General Electric Company | Corrosion resistant composite claddings for nuclear fuel rods |
US5026516A (en) * | 1989-05-25 | 1991-06-25 | General Electric Company | Corrosion resistant cladding for nuclear fuel rods |
US5073336A (en) * | 1989-05-25 | 1991-12-17 | General Electric Company | Corrosion resistant zirconium alloys containing copper, nickel and iron |
US5373541A (en) * | 1992-01-17 | 1994-12-13 | Framatome | Nuclear fuel rod and method of manufacturing the cladding of such a rod |
US5493592A (en) * | 1992-03-13 | 1996-02-20 | Siemens Aktiengesellschaft | Nuclear-reactor fuel rod with double-layer cladding tube and fuel assembly containing such a fuel rod |
WO1993018520A1 (en) * | 1992-03-13 | 1993-09-16 | Siemens Aktiengesellschaft | Nuclear reactor fuel rod with double layer cladding tube |
US5247550A (en) * | 1992-03-27 | 1993-09-21 | Siemens Power Corporation | Corrosion resistant zirconium liner for nuclear fuel rod cladding |
US5887045A (en) * | 1995-01-30 | 1999-03-23 | Framatome | Zirconium alloy tube for a nuclear reactor fuel assembly, and method for making same |
US5711826A (en) * | 1996-04-12 | 1998-01-27 | Crs Holdings, Inc. | Functionally gradient cladding for nuclear fuel rods |
US6319339B1 (en) | 1997-03-25 | 2001-11-20 | Framatome Anp Inc. | High strength zirconium alloys containing bismuth |
US5790623A (en) * | 1997-03-25 | 1998-08-04 | Siemens Power Corporation | Composite cladding for nuclear fuel rods |
US5772798A (en) * | 1997-03-25 | 1998-06-30 | Siemens Power Corporation | High strength zirconium alloys containing bismuth |
US5768332A (en) * | 1997-03-27 | 1998-06-16 | Siemens Power Corporation | Nuclear fuel rod for pressurized water reactor |
US5787142A (en) * | 1997-04-29 | 1998-07-28 | Siemens Power Corporation | Pressurized water reactor nuclear fuel assembly |
US6511556B1 (en) | 1998-06-12 | 2003-01-28 | Siemens Power Corporation | High strength zirconium alloys containing bismuth and niobium |
US20050005872A1 (en) * | 2003-07-09 | 2005-01-13 | Greeson John Stuart | Automated carrier-based pest control system |
US20060048869A1 (en) * | 2004-09-08 | 2006-03-09 | David White | Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same |
US20060048870A1 (en) * | 2004-09-08 | 2006-03-09 | David White | Zirconium alloy fuel cladding for operation in aggressive water chemistry |
US8043448B2 (en) | 2004-09-08 | 2011-10-25 | Global Nuclear Fuel-Americas, Llc | Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same |
US9139895B2 (en) | 2004-09-08 | 2015-09-22 | Global Nuclear Fuel—Americas, LLC | Zirconium alloy fuel cladding for operation in aggressive water chemistry |
US20110002433A1 (en) * | 2006-08-24 | 2011-01-06 | Lars Hallstadius | Water Reactor Fuel Cladding Tube |
US8320515B2 (en) | 2006-08-24 | 2012-11-27 | Westinghouse Electric Sweden Ab | Water reactor fuel cladding tube |
Also Published As
Publication number | Publication date |
---|---|
DE3668251D1 (en) | 1990-02-15 |
EP0212351B1 (en) | 1990-01-10 |
JPH065311B2 (en) | 1994-01-19 |
EP0212351A1 (en) | 1987-03-04 |
JPS6235287A (en) | 1987-02-16 |
DE3528545A1 (en) | 1987-02-19 |
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Legal Events
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AS | Assignment |
Owner name: KRAFTWERK UNION AKTIENGESELLSCHAFT, MULHEIM/RUHR, Free format text: ASSIGNMENT OF ASSIGNORS INTEREST.;ASSIGNORS:STEHLE, HEINZ;STEINBERG, ECKARD;WEIDINGER, HANS;REEL/FRAME:004821/0385 Effective date: 19860717 Owner name: SIEMENS AKTIENGESELLSCHAFT, BERLIN AND MUNICH, GER Free format text: MERGER;ASSIGNOR:KRAFTWERK UNION AKTIENGESELLSCHAFT, (MERGED INTO);REEL/FRAME:004936/0001 Effective date: 19870923 Owner name: KRAFTWERK UNION AKTIENGESELLSCHAFT, A GERMAN CORP. Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:STEHLE, HEINZ;STEINBERG, ECKARD;WEIDINGER, HANS;REEL/FRAME:004821/0385 Effective date: 19860717 |
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